NEW NEUTRON DETECTOR BY FISSION IN A FLOWING GAS (in French)
Journal Article
·
· J. Nuclear Energy
With the Instruments and methods described in this paper it is possible to measure, at any time, a flux of slow neutrons in presence of very intense fluxes of gamma -rays: fission products are carried by a gas stream past a BETA -, gamma counter. The minimum measurable flux is of the order of a few thermal neutrons per cm/sup 2/ and per second. The power of a nuclear reactor can be easiIy followed; neutron density maps can be plotted very accurately as soon as fluxes are greater than 10/sup 8//cm/s. Temperature resistance is excellent. (auth)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-12-001521
- OSTI ID:
- 4353487
- Journal Information:
- J. Nuclear Energy, Journal Name: J. Nuclear Energy Vol. Vol: 5
- Country of Publication:
- Country unknown/Code not available
- Language:
- French
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